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压水堆核电厂高压熔堆严重事故序列分析 被引量:19
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作者 张琨 曹学武 《原子能科学技术》 EI CAS CSCD 北大核心 2008年第6期530-534,共5页
压水堆核电厂的高压熔堆事故覆盖了大部分的严重事故序列,且具有很大的潜在威胁。根据我国900 MW压水堆核电厂的概率安全分析(PSA)结果选取了丧失厂外电、未能紧急停堆的预期瞬态、二回路管道破口、一回路小破口和蒸汽发生器传热管破裂... 压水堆核电厂的高压熔堆事故覆盖了大部分的严重事故序列,且具有很大的潜在威胁。根据我国900 MW压水堆核电厂的概率安全分析(PSA)结果选取了丧失厂外电、未能紧急停堆的预期瞬态、二回路管道破口、一回路小破口和蒸汽发生器传热管破裂5种典型的高压熔堆严重事故序列,并使用SCDAP/RELAP5程序对这些事故序列的进程和后果进行了计算分析。计算结果表明:5种典型高压熔堆事故序列可能导致高压熔喷和安全壳直接加热风险,可能引起安全壳早期失效,很有必要采取相应的一回路卸压措施。 展开更多
关键词 900 MW压水堆核电厂 高压熔堆事故 SCDAP/RELAP5程序
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恰希玛核电厂2号机组高压熔堆预防和缓解措施的设计和分析 被引量:1
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作者 史国宝 《核动力工程》 EI CAS CSCD 北大核心 2011年第6期110-114,共5页
恰希玛核电厂2号机组在稳压器上增设一个电动节流阀,用于在"充水-排汽"冷却中实施排汽,以及严重事故高压熔堆下快速降压。本文采用SCDAP/RELAP5/MOD3.1程序分析了全厂断电叠加2个系列柴油机辅助给水系统失效事故,结果表明,增... 恰希玛核电厂2号机组在稳压器上增设一个电动节流阀,用于在"充水-排汽"冷却中实施排汽,以及严重事故高压熔堆下快速降压。本文采用SCDAP/RELAP5/MOD3.1程序分析了全厂断电叠加2个系列柴油机辅助给水系统失效事故,结果表明,增设的稳压器电动节流阀能有效地实施严重事故下快速降压,缓解事故后果。 展开更多
关键词 高压熔堆 缓解措施 快速降压 电动节流阀
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320 MW核电机组SBO事故下高压熔堆应对和缓解能力分析 被引量:2
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作者 黄秋兰 王盟 +2 位作者 严舟 胡海平 刘全友 《核科学与工程》 CAS CSCD 北大核心 2019年第1期101-105,共5页
应用MAAP5程序建立了320 MW核电机组一二回路、安全系统以及安全壳的模型,对SBO事故序列下高压熔堆的缓解能力进行了分析。结果表明:安全壳有能力抵御高压熔堆造成的压力冲击,采用稳压器安全阀的强制开启策略可以有效缓解高压熔堆,在72 ... 应用MAAP5程序建立了320 MW核电机组一二回路、安全系统以及安全壳的模型,对SBO事故序列下高压熔堆的缓解能力进行了分析。结果表明:安全壳有能力抵御高压熔堆造成的压力冲击,采用稳压器安全阀的强制开启策略可以有效缓解高压熔堆,在72 h内无能动干预手段的条件下,安全壳的完整性可以得到保证,可为320 MW核电机组严重事故预防和事故缓解措施的制定提供重要的参考。 展开更多
关键词 MAAP5 320 MW核电机组 高压熔堆事故 安全壳 完整性
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压水堆核电厂严重事故卸压阀能力评估 被引量:2
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作者 邵舸 佟立丽 曹学武 《核科学与工程》 CSCD 北大核心 2015年第1期157-162,共6页
在百万千瓦级压水堆核电厂中为防止高压熔堆严重事故发生时发生高压熔喷(HPME)和安全壳直接加热(DCH),参考EPR堆型在稳压器上额外设置严重事故卸压阀(SADV),对主系统进行快速卸压。建立百万千瓦级压水堆核电厂事故分析模型,选取丧失厂... 在百万千瓦级压水堆核电厂中为防止高压熔堆严重事故发生时发生高压熔喷(HPME)和安全壳直接加热(DCH),参考EPR堆型在稳压器上额外设置严重事故卸压阀(SADV),对主系统进行快速卸压。建立百万千瓦级压水堆核电厂事故分析模型,选取丧失厂外电叠加汽动辅助给水泵失效,一回路管道小破口以及丧失主给水三条典型严重事故序列,进行系统热工水力及卸压能力分析。计算结果表明:如果不开启严重事故卸压阀,三条事故序列在压力容器下封头失效时一回路压力均较高,有发生高压熔喷和安全壳直接加热的风险。根据严重事故管理导则开启严重事故卸压阀,可以有效降低一回路压力,三条事故序列均可以防止高压熔喷和安全壳直接加热发生。针对卸压阀阀门面积的影响进行分析,表明阀门面积减小到4.8×10-3 m2后下封头失效时RCS压力会有所增加,仍然能够满足RCS的卸压要求,且可延迟下封头失效时间。 展开更多
关键词 严重事故卸压阀 高压熔堆 快速卸压
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反应堆主回路卸压对压力容器外裂变产物释放的影响分析 被引量:1
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作者 邵舸 佟立丽 曹学武 《原子能科学技术》 EI CAS CSCD 北大核心 2013年第7期1187-1191,共5页
本工作耦合建立了600MW压水堆核电厂热工水力、裂变产物行为和放射性后果评价的分析模型,选取SB-LOCA、SGTR、SBO和LOFW等4个高压熔堆事故序列,研究了主回路卸压对压力容器外裂变产物释放的影响,包括主回路卸压对压力容器外裂变产物释... 本工作耦合建立了600MW压水堆核电厂热工水力、裂变产物行为和放射性后果评价的分析模型,选取SB-LOCA、SGTR、SBO和LOFW等4个高压熔堆事故序列,研究了主回路卸压对压力容器外裂变产物释放的影响,包括主回路卸压对压力容器外裂变产物释放的缓解效应和其他负面影响。分析表明:实施主回路卸压可缓解高压熔堆事故序列下压力容器外的释放,但卸压工况下事故早期安全壳内的气载放射性活度较基准工况下的大。相关分析结论可作为严重事故管理导则制定的技术基础。 展开更多
关键词 主回路卸压 压力容器外释放 高压熔堆事故 缓解 负面影响
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严重事故专用卸压阀排放能力需求
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作者 武铃珺 邓坚 +3 位作者 张航 王小吉 刘丽莉 青涛 《强激光与粒子束》 CAS CSCD 北大核心 2021年第7期131-136,共6页
二代加百万千万级核电站严重事故下卸压过程中高温流体流经卸压阀,可能造成流道变形,甚至造成阀杆下落使得排放流道封闭,造成卸压失败。对严重事故专用卸压阀在卸压过程中可能经历的高温流体状态进行谱分析,获得了不同卸压能力下阀门经... 二代加百万千万级核电站严重事故下卸压过程中高温流体流经卸压阀,可能造成流道变形,甚至造成阀杆下落使得排放流道封闭,造成卸压失败。对严重事故专用卸压阀在卸压过程中可能经历的高温流体状态进行谱分析,获得了不同卸压能力下阀门经受的高温流体状态。开展了高温可能引起的阀门流道变形对卸压效果的影响分析。第二类阀门虽然存在阀门流道变形的可能,但能够获得较长严重事故处置时间,从优化严重事故对策的角度,严重事故专用卸压阀推荐采用第二类阀门排放能力450~600 t/h范围。 展开更多
关键词 高压熔堆 熔融物喷射 反应堆冷却剂系统卸压 严重事故卸压阀 高温流体
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快速卸压阀延迟开启对严重事故进程的影响分析 被引量:1
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作者 武铃珺 彭欢欢 +2 位作者 许幼幼 杜政瑀 武小莉 《科技视界》 2021年第10期111-114,共4页
百万千瓦级核电站设置快速卸压阀,用于严重事故中为反应堆冷却剂系统(RCS)主动卸压,避免高压熔融物喷射(HPME)风险。快速卸压阀设计要求启动信号为堆芯出口温度达到650℃,但在实际执行过程中由于事故条件和严重事故管理导则体系所限,此... 百万千瓦级核电站设置快速卸压阀,用于严重事故中为反应堆冷却剂系统(RCS)主动卸压,避免高压熔融物喷射(HPME)风险。快速卸压阀设计要求启动信号为堆芯出口温度达到650℃,但在实际执行过程中由于事故条件和严重事故管理导则体系所限,此时刻立即执行阀门启动操作的可能性不大。文章采用完全丧失给水叠加多重安全功能失效为基准事故序列进行快速卸压阀延迟开启时间谱分析,研究延迟开启对卸压效果及严重事故进程的影响,结果显示,阀门开启时间的延迟不影响快速卸压阀最终的卸压效果,严重事故中,在有效时间内开启阀门为RCS卸压均可以实现预防HPME的卸压目标。 展开更多
关键词 高压熔堆 严重事故卸压 快速卸压阀 延迟开启 安注箱注入
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快速成形技术的发展与应用
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作者 刘冠权 程俊廷 刘帅军 《煤矿机械》 北大核心 2002年第12期1-3,共3页
随着现代信息社会的到来,制造行业的竞争日趋激烈。产品更新速度不断加快,生产方式日趋小批量、多品种。快速成形技术在此背景下产生并得到迅速发展。详细论述了快速成形技术的产生、发展以及目前国内、国外的应用情况,同时对快速成形... 随着现代信息社会的到来,制造行业的竞争日趋激烈。产品更新速度不断加快,生产方式日趋小批量、多品种。快速成形技术在此背景下产生并得到迅速发展。详细论述了快速成形技术的产生、发展以及目前国内、国外的应用情况,同时对快速成形技术的发展前景与展望作了简单介绍。 展开更多
关键词 快速成形技术 层迭法 粉末烧结法 熔堆 制造行业 发展趋势 CAD
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DECISION-MAKING OF SLICING SCHEME IN FUSED DEPOSITION MODELING PROCESS BASED ON ANALYTICAL HIERARCHICAL PROCESS 被引量:6
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作者 张剑峰 彭安华 《Transactions of Nanjing University of Aeronautics and Astronautics》 EI 2010年第2期125-130,共6页
Based on analyzing the influences of a slicing scheme on stair-stepping effect, supporting structure, efficiency and deformation, etc. , analytical hierarchical process (AHP) combining with fuzzy synthetic evaluatio... Based on analyzing the influences of a slicing scheme on stair-stepping effect, supporting structure, efficiency and deformation, etc. , analytical hierarchical process (AHP) combining with fuzzy synthetic evaluation is introduced to make decision in slicing schemes for a processing part. The application in determining the slicing scheme for a computer mouse during prototyping shows that the method increases the rationality during decision- making and improves quality and efficiency for the prototyping part. 展开更多
关键词 DECISION-MAKING fused deposition modeling (FDM) analytical hierarchical process (AHP) slicing scheme
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核电厂直接安全壳加热事故的数值模拟与分析
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作者 李治刚 钟明君 +1 位作者 林萌 杨燕华 《核科学与工程》 CAS CSCD 北大核心 2015年第4期675-681,共7页
文章采用三维多相流数值计算软件,建立AP1000核电厂模型,对高压熔堆严重事故下可能发生的直接安全壳加热(DCH)现象进行模拟和分析。为了能准确预测事故现象,本文结合全厂断电事故后期参数和AP1000核岛几何模型,考虑压力容器内存在冷却... 文章采用三维多相流数值计算软件,建立AP1000核电厂模型,对高压熔堆严重事故下可能发生的直接安全壳加热(DCH)现象进行模拟和分析。为了能准确预测事故现象,本文结合全厂断电事故后期参数和AP1000核岛几何模型,考虑压力容器内存在冷却剂和不存在冷却剂两种工况,模拟事故过程。计算安全壳内气体温度场、熔滴体积份额场以及压力随时间的变化。结果表明:直接安全壳加热事故会在短时间内引起安全壳压力和局部温度的迅速上升;在本文中压力容器内存在冷却剂会加剧DCH现象的后果,但不会威胁安全壳的完整性。 展开更多
关键词 直接安全壳加热 高压熔堆 AP1000核电厂
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The General Design and Technology Innovations of CAP1400 被引量:3
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作者 郑明光 严锦泉 +3 位作者 申屠军 田林 王煦嘉 邱忠明 《Engineering》 SCIE EI 2016年第1期103-111,共9页
A historical review of in-vessel melt retention (IVR) is given, which is a severe accident mitigation mea- sure extensively applied in Generation III pressurized water reactors (PWRs). The idea of IVR actually ori... A historical review of in-vessel melt retention (IVR) is given, which is a severe accident mitigation mea- sure extensively applied in Generation III pressurized water reactors (PWRs). The idea of IVR actually originated from the back-fitting of the Generation 11 reactor Loviisa WER-440 in order to cope with the core-melt risk. It was then employed in the new deigns such as Westinghouse APIO00, the Korean APR1400 as well as Chinese advanced PWR designs HPRIO00 and CAP1400. The most influential phe- nomena on the IVR strategy are in-vessel core melt evolution, the heat fluxes imposed on the vessel by the molten core, and the external cooling of the reactor pressure vessel (RPV). For in-vessel melt evolution, past focus has only been placed on the melt pool convection in the lower plenum of the RPV; however, through our review and analysis, we believe that other in-vessel phenomena, including core degradation and relocation, debris formation, and coolability and melt pool formation, may all contrib- ute to the final state of the melt pool and its thermal loads on the lower head. By looking into previous research on relevant topics, we aim to identify the missing pieces in the picture. Based on the state of the art, we conclude by proposing future research needs. 展开更多
关键词 Pressurized water reactor Severe accident In-vessel melt retention Debris formationDebris remeltingMelt pool formationMelt pool thermal-hydraulicsCritical heat flux
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The Coolibility of Melt Pool in PWR Lower Head - Results of LIVE Experiments
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作者 X. Gaus-Liu A. Miassoedov T. Cron T. Wenz 《Journal of Energy and Power Engineering》 2010年第3期15-21,共7页
The LIVE (Late In-Vessel Phase Experiments) test program investigates in-vessel melt pool behaviour and cooling strategies for in-vessel corium retention during severe accidents in light water reactors (LWR). The ... The LIVE (Late In-Vessel Phase Experiments) test program investigates in-vessel melt pool behaviour and cooling strategies for in-vessel corium retention during severe accidents in light water reactors (LWR). The main part of the LIVE facility is a 1:5 scaled semi-spherical lower head of a typical pressurized water reactor. Up to now, LIVE experiments have been performed in different initial external cooling conditions, melt volumes and internal heat generations. At present the well-known simulant material KNO3-NaNO3 in non-eutectic composition (80 mole% KNO3-20 mole% NaNO3) and in eutectic composition (50 mole% KNO3- 50 mole% NaNO3) is used in the live program. The 3D heat flux distribution through vessel wall, melt pool temperature, crust thickness and the pool melt composition can be measured or determined. Extensive results have been obtained concerning the melt pool thermal hydraulic behaviour in transient and in steady state conditions. 展开更多
关键词 Core melt LWR in vessel corium retention PWR lower head
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Use of Thorium in the Generation IV Molten Salt Reactors and Perspectives for Brazil
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作者 Jose Antonio Seneda Paulo Ernesto Oliveira Lainetti 《Journal of Energy and Power Engineering》 2014年第10期1655-1662,共8页
Interest in thorium stems mainly from the fact that it is expected to have a substantial increase in uranium prices. So, advanced fuel cycles which increase the reserves of nuclear materials are interesting, particula... Interest in thorium stems mainly from the fact that it is expected to have a substantial increase in uranium prices. So, advanced fuel cycles which increase the reserves of nuclear materials are interesting, particularly, the use of thorium is to produce the fissile isotope ^233U. Thorium is three to five times more abundant than uranium in the earth's crust. Additionally, thoria produces less radiotoxicity than the UO2, because it produces fewer amounts of actinides. ThO2 has higher corrosion resistance, besides being chemically stable, and the burning of Pu in a reactor based in thorium also decreases the inventories of Pu from the current fuel cycles. There are some ongoing projects in the world, taking into consideration the proposed goals for Generation IV reactors, namely: sustainability, economics, safety and reliability, proliferation resistance and physical protection. Some developments on the use of thorium in reactors are underway, with the support of the IAEA (International Atomic Energy Agency) and some govern like molten salt reactor. In this paper, we discuss the future importance of thorium, particularly for Brazil, which has large mineral reserves of this strategic element, the characteristics of the molten salt reactor and the experience of the IPEN (Instituto de Pesquisas Energ6ticas e Nucleares) in the purification of thorium compounds. 展开更多
关键词 Molten salt reactor Generation IV reactors THORIUM uranium-233.
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Molten waste plastic pyrolysis in a vertical falling film reactor and the influence of temperature on the pyrolysis products 被引量:2
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作者 zechen jin dezhen chen +3 位作者 lijie yin yuyan hu huangqing zhu liu hong 《Chinese Journal of Chemical Engineering》 SCIE EI CAS CSCD 2018年第2期400-406,共7页
Molten plastics are characterised with high viscosity and low thermal conductivity. Applying falling film pyrolysis reactor to deal with waste plastics can not only improve heat transfer efficiency, but also solve the... Molten plastics are characterised with high viscosity and low thermal conductivity. Applying falling film pyrolysis reactor to deal with waste plastics can not only improve heat transfer efficiency, but also solve the flow problem. In this work, the pyrolysis process of molten polypropylene (PP) in a vertical falling film reactor is experimentally studied, and the influence of heating temperature on pyrolysis products is discussed. It has been found that with the temperature increases from 550 ℃ to 625 ℃, the yield of pyrolysis oil decreases from 74.4 wt% ( 4- 2.2 wt/%) to 53.5 wt% (± 1.3 wt%). The major compositions of the pyrolysis oil are C9, C12 and C18, and β-scission reactions are predominant. The content of the light fraction C6-C12 of pyrolysis oil is 69.7 wt%. Compared with other pyrolysis reactors, the yield ofoil from vertical falling film pyrolysis reactor is slightly higher than that from tubular reactor, equal to that from rotary kiln reactor, and slightly lower than that in medium fluidised-bed reactor. 展开更多
关键词 Pyrolysis Reactor Molten plastic Pyrolysis oil Fractional condensation
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Numerical Simulation of MHD Jet Flows
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作者 KANG Weishan XU Zengyu PAN Chuanjie 《Southwestern Institute of Physics Annual Report》 2004年第1期109-110,共2页
Liquid metal free surface flows (films, jets and droplets) are considered as diverter/ limiter system and first wall in fusion reactor, but the knowledge Of liquid metal free surface under a non-uniform magnetic fie... Liquid metal free surface flows (films, jets and droplets) are considered as diverter/ limiter system and first wall in fusion reactor, but the knowledge Of liquid metal free surface under a non-uniform magnetic field is very limited. In this article, the stability of a jet flow under a gradient magnetic field is investigated, and its MHD effects are the top concern. Based on numerical simulation and experimental results, a simplified model is developed to analyze the MHD effects of the jet flow and to explain the reason why it can keep stable under a strong non-uniform magnetic field. 展开更多
关键词 MHD Liquid metal Jet flows
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Effects of Thermal Treatments on Helium Retention and Thermal Desorption Behaviors in a V-4Ti Aalloy
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作者 LIU Xiang T. Yamada T. Hino 《Southwestern Institute of Physics Annual Report》 2004年第1期102-105,共4页
Vanadium alloys are considered as the promising first wall and structure materials of the future fusion reactors owing to their perfect low neutron-induced radioactivity and good high temperature performance. Helium r... Vanadium alloys are considered as the promising first wall and structure materials of the future fusion reactors owing to their perfect low neutron-induced radioactivity and good high temperature performance. Helium retention and thermal desorption behaviors are key issues for the applications of vanadium alloys in fusion reactors since helium can be produced by helium discharge cleaning and neutron transmutation. A. van Veen groupt investigated helium trapping and thermal desorption mechanisms in vanadium alloys by using 1 keV helium ion irradiation to the fluence of 10^13~10^14He/cm^2, and the influenee of pre-annealing treatments on helium trapping. Two group of peaks were found at the thermal helium desorption spectrum. They thought one was due to helium-vacancyimpurity clusters and the other was corresponding to helium trapping into pre-existing traps, such as fine-size precipitates. 展开更多
关键词 Vanadium alloy TDS Thermal treatment
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Behavior of Hydrogen and Nitrogen in Tungsten, as Divertor Wall of a Fusion Reactor
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作者 Sergio Beneitez Juana L. Gervasoni Carlos Furnari 《Journal of Energy and Power Engineering》 2018年第1期16-25,共10页
The analysis of the interaction of hydrogen, nitrogen (and their isotopes) with tungsten is important, since this material is a strong candidate to form the first wall of fusion reactors for both magnetic and inerti... The analysis of the interaction of hydrogen, nitrogen (and their isotopes) with tungsten is important, since this material is a strong candidate to form the first wall of fusion reactors for both magnetic and inertial confinement, and these atoms have a very sensitive (desired and unwanted) interaction with it. For this purpose, we study the effects and electronic state densities of atomic hydrogen and nitrogen in pure tungsten, in order to analyze some important properties such as the density of states of the system. Focusing on this application, this work is a preliminary study of the behavior of atoms of hydrogen and nitrogen, on a surface of tungsten on the three sites of the cell: top, hollow and bridge. We use a program simulation based on the DFT (density functional theory) implemented in the Open-Source Code Quantum Espresso, in order to obtain the adsorption energy and the density of states of the systems. 展开更多
关键词 TUNGSTEN electronic properties fusion.
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Hybrid Dynamic Modeling and Control of Molten Carbonate Fuel Cell Stack Shutdown
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作者 李勇 曹广益 朱新坚 《Journal of Donghua University(English Edition)》 EI CAS 2007年第1期35-38,共4页
A hybrid automaton modeling approach that incorporates state space partitioning, phase dynamic modeling and control law synthesis by control strategy is utilized to develop a hybrid automaton model of molten carbonate... A hybrid automaton modeling approach that incorporates state space partitioning, phase dynamic modeling and control law synthesis by control strategy is utilized to develop a hybrid automaton model of molten carbonate fuel cell (MCFC) stack shutdown. The shutdown operation is divided into several phases and their boundaries are decided according to a control strategy, which is a set of specifications about the dynamics of MCFC stack during shutdown. According to the control strategy, the specification of increasing stack temperature is satisfied in a phase that can be modeled accurately. The model for phase that has complex dynamic is approximated. The duration of this kind of phase is decreased to minimize the error caused by model approximation. 展开更多
关键词 MCFC fuel cell hybrid automaton control strategy shutdown.
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小型堆断电严重事故缓解措施分析 被引量:3
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作者 陈航 张帆 +1 位作者 晏峰 王坤 《核动力工程》 EI CAS CSCD 北大核心 2015年第2期62-65,共4页
以典型的小型堆为研究对象,用MELCOR程序对满功率运行的小型堆全部电源丧失严重事故序列进行计算,分析比较几种缓解措施对事故缓解的作用。结果表明:在发生全部电源丧失后,反应堆热阱丧失,并会发生高压熔堆事故,导致安全壳的完整性受到... 以典型的小型堆为研究对象,用MELCOR程序对满功率运行的小型堆全部电源丧失严重事故序列进行计算,分析比较几种缓解措施对事故缓解的作用。结果表明:在发生全部电源丧失后,反应堆热阱丧失,并会发生高压熔堆事故,导致安全壳的完整性受到破坏。若应急电源及时恢复,安全注入系统投入,再循环取海水冷却能有效缓解事故进程。 展开更多
关键词 断电 MELCOR 严重事故 高压熔堆
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百万千瓦级压水堆严重事故卸压阀高温瞬态分析 被引量:2
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作者 王小吉 武铃珺 +3 位作者 吴清 刘丽莉 彭欢欢 邹志强 《核动力工程》 EI CAS CSCD 北大核心 2021年第3期69-73,共5页
由于核电厂严重事故的恶劣工况,在卸压过程中严重事故卸压阀门可能会经历阀门无法承受的高温瞬态而导致不可用。本文在可能导致高压熔堆的事故序列中筛选出具有一定的包络性并包含各种典型严重事故现象的典型严重事故序列。针对该事故... 由于核电厂严重事故的恶劣工况,在卸压过程中严重事故卸压阀门可能会经历阀门无法承受的高温瞬态而导致不可用。本文在可能导致高压熔堆的事故序列中筛选出具有一定的包络性并包含各种典型严重事故现象的典型严重事故序列。针对该事故序列考虑严重事故管理中的开阀时间范围开展了高温瞬态计算,并针对重要的影响因素阀门开启时刻的稳压器水位开展分析。最终确定了百万千瓦级核电厂具备典型性及一定包络性的严重事故卸压阀工作条件,并得到了阀门开启前后阀门可能经历的最高流体温度及流体温度变化曲线,为严重事故卸压阀门的设备鉴定及功能应用提供了重要基础。 展开更多
关键词 严重事故 卸压阀 高压熔堆
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